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Division Spotlight
Radiation Protection & Shielding
The Radiation Protection and Shielding Division is developing and promoting radiation protection and shielding aspects of nuclear science and technology — including interaction of nuclear radiation with materials and biological systems, instruments and techniques for the measurement of nuclear radiation fields, and radiation shield design and evaluation.
Meeting Spotlight
2025 ANS Annual Conference
June 15–18, 2025
Chicago, IL|Chicago Marriott Downtown
Standards Program
The Standards Committee is responsible for the development and maintenance of voluntary consensus standards that address the design, analysis, and operation of components, systems, and facilities related to the application of nuclear science and technology. Find out What’s New, check out the Standards Store, or Get Involved today!
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Latest News
NRC v. Texas: Supreme Court weighs challenge to NRC authority in spent fuel storage case
The State of Texas has not one but two ongoing federal court challenges to the Nuclear Regulatory Commission that could, if successful, turn decades of NRC regulations, precedent, and case law on its head.
Thomas F. Plunkett
Nuclear Technology | Volume 3 | Number 3 | March 1967 | Pages 178-186
Technical Paper and Note | doi.org/10.13182/NT67-A27872
Articles are hosted by Taylor and Francis Online.
The gaseous-core or cavity nuclear reactor is of significant interest for advanced nuclear propulsion because of its high performance capabilities compared to solid-core nuclear and chemical propulsion concepts. By removal of temperature limitations associated with solid materials in the core and by use of radiative transfer as the principal mode of energy transfer from the fuel to the propellant, propellant exhaust temperatures of 7000°K and specific impulses in excess of 2000 sec can be obtained. This article describes a detailed nuclear analysis of a gaseous-core nuclear rocket engine in which the spatial effects of the cavity liner material, coolant tubes, and structural components, as well as neutron streaming out of propellant inlet and outlet (nozzle) passages, are considered. Calculational methods were evaluated, and multigroup diffusion theory was selected. Two-dimensional diffusion and transport calculations are compared for finite cylindrical cavity reactors having both central and annular nozzle exhausts. A parameter study was made of fuel and reflector materials, core and reflector dimensions, and temperature effects. Significant results of this study are: 1) extremely high fuel loadings are required for a propulsion reactor; 2) substantial preheating of the reflector will be required for startup; and 3) uranium-233 has significant advantages over 235U and 239Pu as fuel in gaseous-core nuclear rockets.